Bwxt Mpower, Inc.

Bwxt Isotope Technology Group, Inc.

Bwxt Advanced Technologies LLC

Bwxt Nuclear Energy, Inc.

Earl Brian Barger

Jeffrey T Lee

Scott Lee Fitzner

William Earl Russell, Ii

Roger D Ridgeway

Roger Dale Ridgeway

Bryan Blake Wiggins

Christopher Sean Fewox

Stephen D Preite

Scott James Shargots

Benjamin D Fisher

James Brian Inman

Erik T Nygaard

Timothy A Policke

Barbara B Bohannon

Benjamin I Bishop

Steve W Schilthelm

Ryan Z Ziegler

Michael J Nilles

Emily Fleming

Todd Oswald

William E Ii Russell

William Earl Russell Ii

A process for producing a titanium-molybdate material is provided. The process includes a step of reacting a metal molybdenum (Mo) material in a liquid medium with a first acid to provide a Mo composition and combining the Mo composition with a titanium source to provide a Ti—Mo composition. The Ti—Mo composition can be pH adjusted with a base to precipitate a plurality of Ti—Mo particulates.

Titanium-molybdate and method for making the same

A fuel rod for a nuclear reactor, including a cladding tube having a first end with an annular end face, a second end with an annular end face, and a cylindrical body portion extending therebetween, and a first tube end plug including a front portion, an annular lip with an annular end face, and a substantially straight cylindrical body portion extending therebetween, wherein the surface area of the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are substantially equal, and the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are connected by a resistance pressure weld.

Resistance pressure weld for nuclear reactor fuel rod tube end plug

A nuclear fuel assembly for a nuclear reactor core, the fuel assembly having at least one fuel element including an elongated shell defining an interior volume, a lattice structure disposed within the interior volume, at least one flow channel extending through the lattice structure, at least one lattice site disposed in the lattice structure, and at least one fuel compact disposed within a corresponding one of the at least one lattice site, a first end cap including a boss having a first cross-sectional shape, the first end cap being affixed to a first end of the shell, and a second end cap including a first bore having a second cross-sectional shape, the second end cap being affixed to a second end of the shell, wherein the first cross-sectional shape of the boss is the same as the cross-sectional shape of the bore.

Nuclear reactor fuel assemblies and process for production

An irradiation target for the production of radioisotopes, comprising at least one plate defining a central opening and an elongated central member passing through the central opening of the at least one plate so that the at least one plate is retained thereon, wherein the at least one plate and the elongated central member are both formed of materials that produce molybdenum-99 (Mo-99) by way of neutron capture.

Irradiation targets for the production of radioisotopes

A pellet magazine includes a plurality of pellet bores sized to receive pellets for loading into a fuel rod. A fuel rod loading system includes a plurality of pellet loading stations each designated to load a single pellet type into one or more pellet bores of the pellet magazine, a rod loading station configured to unload pellets from the pellet bores of the pellet magazine into a fuel rod, and a conveyance system configured to transport the pellet magazine to the loading stations and then to the rod loading station in a defined sequence.

Pellet handling apparatus and fuel rod loading method

A system for analyzing radiochemical purity of an eluate produced from a generator is provided. The system has an elution detector made of a shielding metal. The elution detector houses a flow path template for flow of an eluate solution and an elutable isotope contained in the generator, and a monitoring device for simultaneously monitoring the generator and the eluate exiting the generator. The generator is a Technetium-99m (Tc-99m) generator, and the elutable isotope may be contained in a packed bed of a column in the Tc-99m generator. A method for analyzing radiochemical purity of eluate produced from a Technetium-99m (Tc-99m) generator or column is also provided.

System and method for evaluating elution efficiency and radiopurity of tc-99m generators

A control rod drive mechanism for use in a nuclear reactor including a reactor core disposed in a pressure vessel, including a control rod configured for insertion into the reactor core, a lead screw, the control rod being secured to the bottom end of the lead screw, a drive mechanism including a torque tube having a top end and a bottom end, a pair of segment arms that are pivotably mounted to the torque tube, a pair of roller nuts, each roller nut being rotatably secured to the bottom end of a respective segment arm, and a drive motor including a stator and a rotor secured to the top end of the torque tube that includes a plurality of permanent magnets embedded therein, wherein the stator defines a central bore in which the rotor is disposed, and a latch coil assembly including a latch coil, wherein the latch coil assembly defines a central bore in which the top ends of the segment arms are disposed radially-inwardly of the latch coil.

Control rod drive mechanism with separate latch and drive coils

A process for producing a metal-molybdate material is provided. The process includes a step of reacting a metal molybdenum (Mo) material in a liquid medium with a first acid to provide a Mo composition and combining the Mo composition with a metal source to provide a metal-Mo composition. The metal-Mo composition can be pH adjusted with a base to precipitate a plurality of metal-Mo particulates.

Metal-molybdate and method for making the same

An open end of a cladding tube of a nuclear fuel rod is plugged with an end plug having a main body and a cylindrical bond portion extending from the main body and terminating in a cladding seat with reduced diameter compared with the cylindrical bond portion. The plugging includes clamping the open end of the cladding tube against the cladding seat of the end plug and, while clamping, applying electrical current between the end plug and the open end of the cladding tube so as to force the open end of the cladding tube over the cladding seat and slide over the cylindrical bond portion of the end plug and to generate a resistance weld between a cylindrical bonding surface of the cylindrical bond portion of the end plug and the inside surface of the open end of the cladding tube.

Resistance welding of an end cap for nuclear fuel rods

Growing community of inventors

Goode, VA, United States of America

Earl Brian Barger